Grease Soldification Causes Molded-Case Circuit Breaker Failure to Close| ML031080033 |
| Person / Time |
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| Site: |
Beaver Valley, Millstone, Hatch, Monticello, Calvert Cliffs, Dresden, Davis Besse, Peach Bottom, Browns Ferry, Salem, Oconee, Mcguire, Nine Mile Point, Palisades, Palo Verde, Perry, Indian Point, Fermi, Kewaunee, Catawba, Harris, Wolf Creek, Saint Lucie, Point Beach, Oyster Creek, Watts Bar, Hope Creek, Grand Gulf, Cooper, Sequoyah, Byron, Pilgrim, Arkansas Nuclear, Braidwood, Susquehanna, Summer, Prairie Island, Columbia, Seabrook, Brunswick, Surry, Limerick, North Anna, Turkey Point, River Bend, Vermont Yankee, Crystal River, Haddam Neck, Ginna, Diablo Canyon, Callaway, Vogtle, Waterford, Duane Arnold, Farley, Robinson, Clinton, South Texas, San Onofre, Cook, Comanche Peak, Yankee Rowe, Maine Yankee, Quad Cities, Humboldt Bay, La Crosse, Big Rock Point, Rancho Seco, Zion, Midland, Bellefonte, Fort Calhoun, FitzPatrick, McGuire, LaSalle, Fort Saint Vrain, Shoreham, Satsop, Trojan, Atlantic Nuclear Power Plant, Crane  |
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| Issue date: |
01/31/1994 |
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| From: |
Grimes B
Office of Nuclear Reactor Regulation |
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| To: |
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| References |
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| IN-93-026, Suppl 1, NUDOCS 9401250302 |
| Download: ML031080033 (8) |
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Similar Documents at Beaver Valley, Millstone, Hatch, Monticello, Calvert Cliffs, Dresden, Davis Besse, Peach Bottom, Browns Ferry, Salem, Oconee, Mcguire, Nine Mile Point, Palisades, Palo Verde, Perry, Indian Point, Fermi, Kewaunee, Catawba, Harris, Wolf Creek, Saint Lucie, Point Beach, Oyster Creek, Watts Bar, Hope Creek, Grand Gulf, Cooper, Sequoyah, Byron, Pilgrim, Arkansas Nuclear, Braidwood, Susquehanna, Summer, Prairie Island, Columbia, Seabrook, Brunswick, Surry, Limerick, North Anna, Turkey Point, River Bend, Vermont Yankee, Crystal River, Haddam Neck, Ginna, Diablo Canyon, Callaway, Vogtle, Waterford, Duane Arnold, Farley, Robinson, Clinton, South Texas, San Onofre, Cook, Comanche Peak, Yankee Rowe, Maine Yankee, Quad Cities, Humboldt Bay, La Crosse, Big Rock Point, Rancho Seco, Zion, Midland, Bellefonte, Fort Calhoun, FitzPatrick, McGuire, LaSalle, Fort Saint Vrain, Shoreham, Satsop, Trojan, Atlantic Nuclear Power Plant, Crane |
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Category:NRC Information Notice
[Table view]The following query condition could not be considered due to this wiki's restrictions on query size or depth: <code> [[:Beaver Valley]] OR [[:Millstone]] OR [[:Hatch]] OR [[:Monticello]] OR [[:Calvert Cliffs]] OR [[:Dresden]] OR [[:Davis Besse]] OR [[:Peach Bottom]] OR [[:Browns Ferry]] OR [[:Salem]] OR [[:Oconee]] OR [[:Mcguire]] OR [[:Nine Mile Point]] OR [[:Palisades]] OR [[:Palo Verde]] OR [[:Perry]] OR [[:Indian Point]] OR [[:Fermi]] OR [[:Kewaunee]] OR [[:Catawba]] OR [[:Harris]] OR [[:Wolf Creek]] OR [[:Saint Lucie]] OR [[:Point Beach]] OR [[:Oyster Creek]] OR [[:Watts Bar]] OR [[:Hope Creek]] OR [[:Grand Gulf]] OR [[:Cooper]] OR [[:Sequoyah]] OR [[:Byron]] OR [[:Pilgrim]] OR [[:Arkansas Nuclear]] OR [[:Braidwood]] OR [[:Susquehanna]] OR [[:Summer]] OR [[:Prairie Island]] OR [[:Columbia]] OR [[:Seabrook]] OR [[:Brunswick]] OR [[:Surry]] OR [[:Limerick]] OR [[:North Anna]] OR [[:Turkey Point]] OR [[:River Bend]] OR [[:Vermont Yankee]] OR [[:Crystal River]] OR [[:Haddam Neck]] OR [[:Ginna]] OR [[:Diablo Canyon]] OR [[:Callaway]] OR [[:Vogtle]] OR [[:Waterford]] OR [[:Duane Arnold]] OR [[:Farley]] OR [[:Robinson]] OR [[:Clinton]] OR [[:South Texas]] OR [[:San Onofre]] OR [[:Cook]] OR [[:Comanche Peak]] OR [[:Yankee Rowe]] OR [[:Maine Yankee]] OR [[:Quad Cities]] OR [[:Humboldt Bay]] OR [[:La Crosse]] OR [[:Big Rock Point]] OR [[:Rancho Seco]] OR [[:Zion]] OR [[:Midland]] OR [[:Bellefonte]] OR [[:Fort Calhoun]] OR [[:FitzPatrick]] OR [[:McGuire]] OR [[:LaSalle]] OR [[:Fort Saint Vrain]] OR [[:Shoreham]] OR [[:Satsop]] OR [[:Trojan]] OR [[:Atlantic Nuclear Power Plant]] OR [[:Crane]] </code>. |
UNITED STATES NUCLEAR REGULATORY
COMMISSION
OFFICE OF NUCLEAR REACTOR REGULATION
WASHINGTON, D.C. 20555 January 31, 1994 NR2' INFORMATION
NOTICE 93-26, SUPPLEMENT
1: GREASE SOLIDIFICATION
CAUSES MOLDED-CASE
CIRCUIT BREAKER FAILURE TO CLOSE
Addressees
All holders of operating
licenses or construction
permits for nuclear power reactors.
Purpose
The U.S. Nuclear Regulatory
Commission (NRC) is Issuing this information
notice to supplement
information
regarding
a problem with a 400-amp frame, 600-V ac molded-case
circuit breaker manufactured
by General Electric Corporation (GE) (Part No. TJK436Y400)
which failed to close when required due to grease solidification.
It is expected that recipients
will review the information
for applicability
to their facilities
and consider actions, as appropriate, to avoid similar problems.
However, suggestions
contained
in this information
notice are not NRC requirements;
therefore, no specific action or written response is required.Description
of Circumstances
On March 26, 1992, an engineered
safety feature (ESF) actuated at the Nine Mile Point Nuclear Station Unit 2 (NMP2) because of the loss of output power from an uninterruptible
power supply (UPS) while the loads were being transferred
from UPS power to the maintenance
supply power. During the transfer, the maintenance
supply output circuit breaker (CB-4) failed to close, causing a loss of power to the standby gas treatment
system radiation monitoring
cabinet, a false-high
radiation
signal, a group 9 (primary containment
purge system) primary containment
isolation, the loss of a control room fire panel annunciator, and a loss of communication
between the radiation monitoring
system computer and non-Class
IE radiation
monitors.
The operator immediately
took corrective
action to close circuit breaker CB-4 manually to restore the UPS loads. The UPS loads lost power for approximately
12 minutes during the event.After Information
Notice (IN) 93-26 was issued on April 7, 1993, additional
information
was obtained from GE and NMP2. The additional
information
in this supplement
is intended to assist recipients
in determining
the significance
of this potential
failure mode at their facilities.
-s 0900&S 9401250302
- i4 i_ (O3i 03017?1. RETURN TO REGULATGRY
CENTRAL FILES ROO&U
KI < 93-26, Supp. I January 31, 1994 Discussion
Niagara Mohawk Power Corporation, the licensee for Nine Mile Point 2 (LER 92-007-00), and Wyle Laboratories (Report No. 42370-RCCB-I)
determined
that circuit breaker CB-4 had failed to close because the grease used at the pivot points inside the breaker had dried out and solidified.
When the grease dried out, the metal-to-metal
contact areas experienced
increased
friction and eventual gouging. The friction caused the breaker to become increasingly
more difficult
to close, until, finally, the breaker would not close at all. The licensee located all breakers of the same make, model, and year as the one that failed and scheduled
their replacement.
Certain observations
were made in the NMP2 analysis relative to these breakers: 1. The safety function of these breakers is both to open and close automatically.
Normally, the only electrical
safety function of a breaker is its ability to trip. None of the breakers of this type at Nine Mile Point 2 have failed to trip when required.2. Due to the nature of the application
of these molded-case
switches, they were cycled extensively (approximately
200-400 times). This is more than a normal molded-case
circuit breaker used in a distribution
panel.3. The breakers were in close proximity
to the UPS transformers
causing operation
above normal ambient conditions, which may or may not have contributed
to the solidification
of the grease.GE has stated that in early 1980 the soap-based
and clay-based
grease used in this style molded-case
circuit breakers was replaced with a synthetic lubricant
as a product enhancement.
However, older molded-case
circuit breakers using the clay-based
and soap-based
grease may still be in use at other plants, in similar applications.
-V zi 93-26, Supp. 1 January 31, 1994 This information
notice requires no specific action or written response.
If you have any questions
about the information
in this notice, please contact the technical
contact listed below or the appropriate
Office of Nuclear Reactor Regulation (NRR) project manager.nan K. Grimes, Director Division of Operating
Reactor Support Office of Nuclear Reactor Regulation
Technical
contact: Mark D. Pratt, NRR (301) 504-2701 Attachment:
List of Recently Issued NRC Information
Notices
- ~'~IN 93-26, Supp. 1 January 31, 1994 This information
notice requires no specific action or written response.
If you have any questions
about the information
in this notice, please contact the technical
contact listed below or the appropriate
Office of Nuclear Reactor Regulation (NRR) project manager.Odginal fgned by Brian K. Grimes Brian K. Grimes, Director Division of Operating
Reactor Support Office of Nuclear Reactor Regulation
Technical
contact: Mark D. Pratt, NRR (301) 504-2701 Attachment:
List of Recently Issued NRC Information
Notices EELB Concurrence
obtained by M.D. Pratt*EELB:DE:NRR
MDPratt 12/22/93*D/DE WHodges 01/12/94 SC/EELB:DE:NRR
C/EELB:DE:NRR
EWWeiss* CHBerlinger*
/~NECampbell
12/17/93*C/OGCB:DORS:NRR
/D RR GHMarcus 12/22/93 "01k (/94*RPB:ADM Tech Ed 12/22/93 DOCUMENT NAME: 93-26SP1.IN
r- IN 93-26, Supp. 1 January xx, 1994 This information
notice requires no specific action or written response.
If you have any questions
about the information
in this notice, please contact the technical
contact listed below or the appropriate
Office of Nuclear Reactor Regulation (NRR) project manager.Brian K. Grimes, Director Division of Operating
Reactor Support Office of Nuclear Reactor Regulation
Technical
contact: Mark D. Pratt, NRR (301) 504-2701 Attachment:
List of Recently Issued NRC Information
Notices EELB Concurrence
obtained by M.D. Pratt*EELB:DE:NRR
MDPratt 12/22/93 D/DE , WHodge'V'W
01/12./94 DOCUMENT NAME: SC/EELB:DE:NRR
EWWeiss*C/OGCB:DORS:NRR
GHMarcus 12/22/93 MCCBSUPP.NEC
C/EELB:DE:NRR
CHBerlinger
/ /D/DORS:NRR
BKGrime'l 01/ /94X*OGCB:DORS:NRR
NECampbell
12/17/93*RPB: ADM Tech Ed 12/22/93 I
IN 93-XX December xx, 1993 This information
notice requires no specific action or written response.
If you have any questions
about the information
in this notice, please contact the technical
contact listed below or the appropriate
Office of Nuclear Reactor Regulation (NRR) project manager.Brian K. Grimes, Director Division of Operating
Reactor Support Office of Nuclear Reactor Regulation
Technical
contact: Mark D. Pratt, NRR (301) 504-2701 Attachment:
List of Recently Issued NRC Information
Notices (FEELB Concurrence
obtained by M.D. Pratt ./A /Ie/w/Z3 EELB:DE:NRR
MDPrat 4 H&y D/DORS:NRR
BKGrimes 12/ /93 DOCUMENT NAME: SC/EELB:DE:NRR
EWWeiss #)C/OGCB:DORS:NRR
GHMarcusmf-I
12/2.2./93 MCCBSUPP.
NEC C/EELB:DE:NRR
CHBerl ingerg'l l OGCB:DORS:NRR
NECampbell
12/rP/93 3'RPB:ADM V Tech Ed (;/ lvq3 IN 93-XX December xx, 1993 This information
notice requires no specific action or written response.
If you have any questions
about the information
in this notice, please contact the technical
contact listed below or the appropriate
Office of Nuclear Reactor Regulation (NRR) project manager.Brian K. Grimes, Director Division of Operating
Reactor Support Office of Nuclear Reactor Regulation
Technical
contact: Mark D. Pratt, NRR (301) 504-2701 Attachment:
List of Recently Issued NRC Information
Notices GEELB Concurrence
obtained by EELB:DE:NRR
SC/EELB:DE:NRR
MDPratt& EWWeisst)D/DORS:NRR
C/OGCB: DORS:NRI BKGrimes GHMarcus 12/ /93 12/ /93 DOCUMENT NAME: MCCBSUPP.NEC
M.D. Pratt C/EELB:DE:NRR
CHBerlingeiO
I1/OGCB:DORS:NRR
NECampbell
12/17/93 4.C.RPB:ADM TechEO R
Attaci t IN 93-26, Supp. 1 January 31, 1994 Page I of I LIST OF RECENTLY ISSUED NRC INFORMATION
NOTICES Informati0n, -Date of Notice No. Subject Issuance Issued to 94-07 93-85, Rev. 1 Solubility
Criteria for Liquid Effluent Releases to Sanitary Sewerage Under the Revised 10 CFR Part 20 Potential
Failure of Long-Term
Emergency Nitrogen Supply for the Automatic
Depressurization
System Valves Problems with X-Relays in DB- and DHP-Type Circuit Breakers Manu-factured by Westinghouse
Potential
Failure of Steam Generator
Tubes with Kinetically
Welded Sleeves Digital Integrated
Circuit Sockets with Intermittent
Contact Deficiencies
Identified
during Service Water System Operational
Performance
Inspections
Inoperability
of General Electric Magne-Blast
Breaker Because of Mis-alignment
of Close-Latch
Spring Turbine Blade Failures Caused by Torsional Excitation
from Electrical
System Disturbance
01/28/94 01/28/94 01/20/94 01/19/94 01/14/94 01/11/94 01/07/94 01/07/94 All byproduct
material and fuel cycle licensees
with the exception
of licensees authorized
solely for sealed sources.All holders of OLs or CPs for boiling water reactors.All holders of OLs or CPs for nuclear power reactors.All holders of OLs or CPs for pressurized
water reactors (PWRs).All NRC licensees
except licensed operators.
All holders of OLs or CPs for nuclear power reactors.All holders of OLs or CPs for nuclear power reactors.All holders of OLs or CPs for nuclear power reactors.94-04 94-03 94-02 OL e Operating
License CP = Construction
Permit
|
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| list | - Information Notice 1993-01, Accuracy of Motor-Operated Valve Diagnostic Equipment Manufactured by Liberty Technologies (4 January 1993)
- Information Notice 1993-02, Malfunction of a Pressurizer Code Safety Valve (4 January 1993, Topic: Loop seal)
- Information Notice 1993-04, Investigation and Reporting of Misadministrations by the Radiation Safety Officer (7 January 1993, Topic: Uranium Hexafluoride, Overexposure)
- Information Notice 1993-05, Locking of Radiography Exposure Devices (14 January 1993, Topic: Uranium Hexafluoride, Inattentive)
- Information Notice 1993-06, Potential Bypass Leakage Paths Around Filters Installed in Ventilation Systems (22 January 1993)
- Information Notice 1993-07, Classification of Transportation Emergencies (1 February 1993)
- Information Notice 1993-08, Failure of Residual Heat Removal Pump Bearings Due to High Thrust Loading (1 February 1993, Topic: Probabilistic Risk Assessment)
- Information Notice 1993-09, Failure of Undervoltage Trip Attachment on Westinghouse Model DB-50 Reactor Trip Breaker (2 February 1993, Topic: Commercial Grade)
- Information Notice 1993-10, Dose Calibrator Quality Control (2 February 1993, Topic: Uranium Hexafluoride)
- Information Notice 1993-11, Single Failure Vulnerability of Engineered Safety Features Actuation Systems (4 February 1993)
- Information Notice 1993-12, Off-Gassing in Auxiliary Feedwater System Raw Water Sources (11 February 1993)
- Information Notice 1993-13, Undetected Modification of Flow Characteristics in High Pressure Safety Injection System (16 February 1993)
- Information Notice 1993-14, Clarification of 10 CFR 40.22, Small Quantities of Source Material (18 February 1993)
- Information Notice 1993-15, Failure to Verify the Continuity of Shunt Trip Attachment Contacts in Manual Safety Injection and Reactor Trip Switches (18 February 1993)
- Information Notice 1993-16, Failures of Not-Locking Devices in Check Valves (19 February 1993, Topic: Anchor Darling, Flow Induced Vibration)
- Information Notice 1993-17, Safety Systems Response to Loss of Coolant and Loss of Offsite Power (25 March 1994, Topic: Loss of Offsite Power, Backfit, Water hammer)
- Information Notice 1993-18, Portable Moisture-Density Gauge User Responsibilities During Field Operations (10 March 1993, Topic: Moisture Density Gauge, Moisture-Density Gauge, Stolen)
- Information Notice 1993-19, Slab Hopper Bulging (17 March 1993, Topic: Hydrostatic)
- Information Notice 1993-20, Thermal Fatigue Cracking of Feedwater Piping to Steam Generators (24 March 1993, Topic: Thermal fatigue)
- Information Notice 1993-21, Summary of NRC Staff Observations Compiled During Engineering Audits or Inspections of Licensee Erosion/Corrosion Programs (25 March 1993, Topic: Weld Overlay, Reactive Inspection)
- Information Notice 1993-22, Tripping of Klockner-Moeller Molded-Case Circuit Breakers Due to Support Lever Failure (26 March 1993, Topic: Commercial Grade)
- Information Notice 1993-23, Weschler Instruments Model 252 Switchboard Meters (31 March 1993, Topic: Commercial Grade)
- Information Notice 1993-24, Distribution of Revision 7 of NUREG-1021, Operation Licensing Examiner Standards (31 March 1993, Topic: Job Performance Measure)
- Information Notice 1993-25, Electrical Penetration Assembly Degradation (1 April 1993)
- Information Notice 1993-26, Grease Soldification Causes Molded-Case Circuit Breaker Failure to Close (31 January 1994)
- Information Notice 1993-27, Level Instrumentation Inaccuracies Observed During Normal Plant Depressurization (8 April 1993, Topic: Reactor Vessel Water Level)
- Information Notice 1993-28, Failure to Consider Loss of DC Bus in the Emergency Core Cooling System Evaluation May Lead to Nonconservative Analysis (9 April 1993, Topic: Loss of Offsite Power, Fuel cladding)
- Information Notice 1993-29, Problems with the Use of Unshielded Test Leads in Reactor Protection System Circuitry (12 April 1993)
- Information Notice 1993-30, NRC Requirements for Evaluation of Wipe Test Results; Calibration of Count Rate Survey Instruments (12 April 1993)
- Information Notice 1993-31, Training of Nurses Responsible for the Care of Patients with Brachytherapy Implants (13 April 1993, Topic: Brachytherapy)
- Information Notice 1993-32, Nonconservative Inputs for Boron Dilution Events Analysis (21 April 1993, Topic: Shutdown Margin)
- Information Notice 1993-33, Potential Deficiency of Certain Class Ie Instrumental and Control Cables (28 April 1993)
- Information Notice 1993-33, Potential Deficiency of Certain Class IE Instrumental and Control Cables (28 April 1993)
- Information Notice 1993-34, Potential for Loss of Emergency Cooling Function Due to a Combination of Operational and Post-LOCA Debris in Containment (6 May 1993, Topic: Brachytherapy)
- Information Notice 1993-35, Insights from Common-Cause Failure Events (12 May 1993, Topic: Probabilistic Risk Assessment)
- Information Notice 1993-36, Notifications, Reports, and Records of Misadministrations (7 May 1993, Topic: Brachytherapy)
- Information Notice 1993-37, Eyebolts with Indeterminate Properties Installed in Limitorque Valve Operator Housing Covers (19 May 1993)
- Information Notice 1993-38, Inadequate Testing of Engineered Safety Features Actuation Systems (24 May 1993)
- Information Notice 1993-39, Radiation Beams From Power Reactor Biological Shields (25 May 1993)
- Information Notice 1993-39, Radiation Beams from Power Reactor Biological Shields (25 May 1993)
- Information Notice 1993-40, Fire Endurance Test Results for Thermal Ceramics FP-60 Fire Barrier Material (26 May 1993, Topic: Safe Shutdown, Fire Barrier, Fire Protection Program)
- Information Notice 1993-41, One Hour Fire Endurance Test Results for Thermal Ceramics Kaowool, 3M Company FS-195 and 3M Company Interam E-50 Fire Barrier Systems (28 May 1993, Topic: Safe Shutdown, Fire Barrier)
- Information Notice 1993-42, Failure of Anti-Rotation Keys in Motor-Operated Valves Manufactured by Yelan (9 June 1993)
- Information Notice 1993-43, Use of Inappropriate Lubrication Oils in Satety-Related Applications (10 June 1993, Topic: Commercial Grade)
- Information Notice 1993-44, Operational Challenges During a Dual-Unit Transient (15 June 1993, Topic: Shift Technical Advisor)
- Information Notice 1993-45, Degradation of Shutdown Cooling System Performance (16 June 1993, Topic: Local Leak Rate Testing)
- Information Notice 1993-46, Potential Problem with Westinghouse Rod Control System and Inadvertent Withdrawal of Single Rod Control Cluster Assembly (10 June 1993)
- Information Notice 1993-47, Unrecognized Loss of Control Room Annunciators (18 June 1993)
- Information Notice 1993-48, Failure of Turbine-Driven Main Feedwater Pump to Trip Because of Contaminated Oil (6 July 1993, Topic: Water hammer)
- Information Notice 1993-49, Improper Integration of Software Into Operating Practices (8 July 1993)
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